ML20245H565

Requests That Encl LC Rouse 890808 Memo Forwarding Amend 13 to License SNM-33,authorizing Facility Startup & Testing of Pellet Production Lines,Be Placed in Docket of Proceeding & Served to Parties.W/Certificate of Svc.Served on 890815

ML20245H565
Person / Time
Site:	07000036
Issue date:	08/15/1989
From:	Becchoefer C Atomic Safety and Licensing Board Panel
To:	Julian E NRC OFFICE OF THE SECRETARY (SECY)
References
CON-#389-9042 MLA, NUDOCS 8908170179
Download: ML20245H565 (12)

Text

T '- - _ _ _ _ _ _ ___ -

=

A,*hD,w#

y . . .  % UNITED $TATES 5 E pgg[7[p E -

NUCLEAR REGULATORY COMMISSION usiP.r ATOMIC SAFETY AND LICENSING BOARD PANEL

'g'i.....,/ wassincrou.o.c.20sss

'89 Als 15 P2 :06 August 15, 1989

(.F r

?X t

NOTE TO: Emile Julian, Actinct Chief Docketing and Service Branch SERVED AUG 1 5 1989 '

Office of the Secretary FROM: Charles Bechhoefcr, ASLBP re: Combustion Engineering, Inc.

(Hematite Fuel Fabrication Facility License No. SNM-33) - Docket No. 70-36-MLA In accordance with our telephone conversation of August 14, 1989, please place the attached document in the i

d cket of this proceeding and serve all parties and petitioners (assuming that parties and petitioners have not already been served).

/D h b v&&& 1 Hm$xh,/ ~

Charles Bechhoefer #

Presiding Officer ADMINISTRATIVE JUDGE

Attachment:

Memo dated.8/8/88 from NMSS 8908170179 g90815

{DR ADOCK 07000036 PDR gb '

~

p ag.. .

l-

[ '

~ k' p, UNITED STATES NUCLEAR REGULATORY COMMISSION 7,

a i j- WASHINGTON. D C. 20555 9

• • • • • AUG eim 1:

MEMORANDUM FOR: Charles Bechhoefer, Esq.

Administrative Judge

, Atomic Safety and Licensing Board  !

Leland C. Rouse, Chief FROM:

Fuel Cycle Safety Branch '

Division of Industrial and Medical Nuclear Safety, NMSS

SUBJECT:

ISSUANCE OF AMENDMENT NO. 13 TO LICENSE N0. 5NM-33, COMBUSTION ENGINEERING. INC. (ASLAP NO. 89-503-01-MLA) i l

As advised by the Office of General Counsel, we have enclosed for your  !

information a copy of the licensing action issued on July 28, 1989, to Combustion Engineerisig, Inc., License No. SNM-33, Amendment No. 13, authorizing i the startup and testing phase only of the new pellet production lines at the Hematite facility.

@d -

Leland C. Rouse, Chief Fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety, NMSS l

Enclosure:

As stated l

I N

L

\

a_-__.-.-._-_-._ _ _ _ _ _ _ _ . - - _ _ _ . . _ - . - _ . - _ _ _ . _ _ _ .

'.. W"

,/ 'o g UNITED STATES a o-

$ $ NUCLEAR REGULATORY COMMISSION WASHINGTON, D C. 20555

..... JUL 2 8 E Docket No. 70-3G-License No. SNM-33 Amendment No. 13 Combustion Engineering. Inc.

ATTN: Mr. J. A. Rode, Plant Manager Hematite Fuel Manufacturing 1000 Prospect Hill Road Windsor, CT 06095-0500 Gentlemen:

In accordance with the amendment application dated March 22, 1989, and pursuant to Title 10, Code of Federal Regulations, Part 70, Materials License No. SNM-33 is hereby amended to authorize the startup and testing of the new pellet production lines with depleted uranium and storage of licensed material in Building 256-2. Accordingly, Condition 9 is revised to include the date of March 22, 1989.

All other conditions of the license shall remain the same.

Revised License No. SNM-33 incorporating Amendment No.13 and our Safety Evaluation Report are enclosed.

This amendment is issued following preparation of an Environmental Assessment related to the proposed action. Based on this assessment, a Finding of No Significant Impact has been prepared and approved pursuant to 10 CFR Part 51.

Copies of this Finding, which was published in the Federal Register on May 24, 1989, and the supporting Environmental Assessment were forwarded to you on May 18, 1989.

L _ ----- _-

l i l

l 00L 2 81989 t

, Mr. J. A. Rode l

)

,- Please with note that depleted this amendment only authorizes the startup and testing phase uranium.

!' Your amendment application dated May 1,1989, requesting authorization for full scale production with enriched ur.anium has not been approved and is under consideration by NRC staff.  ;

FOR THE NUCLEAR REGULATORY COP 9tISSION L w .

M Leland C. Rouse Chief l Fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety, NMSS

Enclosures:

1. Revised License No. SNM-33

2. Safety Evaluation Report cc w/ encls:

Mr. A. E. Scherer, Director Mr. C. B. Brinkman, Manager Nuclear Licensing Washington Nuclear Operations Dr. P. L. ?icGill, Vice President Mr. H. E. Eskridge, Supervisor Nuclear fuel Licensing, Safety and Accountability

^

g _____________________________________________________

NRC Form 374 l 15 84 part 5 U.S. NUCLEA'1 C:EGULATORY CoMMISEG~f or PAma i

l MATERIALS UCENSE l Code of Federal Regulations, Chapter 1, Parts 30,31,3 g

I heretofore made by the licensee, a license is hereby issued authorizing the licensee to r-ceive, acq I source. and special nuclear material designated below; to use such material for the purpose (s) and at the pla I deliver or transfer such material to persons authorized to receive it in accordance with the regulations of license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as l subject to all applicable rules, regulations and orders of the Nuclear Regulatory Commission now or he

conditions specified below.

t

,I Licensee I

l

1. Combustion Engineering, Inc. SNM-33 y 3. License number I Amendment No. 13 I

2. P. O. Box 107 ,

Hematite, Missouri '

l 63047

4. Ekpirs'tidaliste *

• y .N

, 5. Docket or yy 70-36 Reference No. i I 6. Byproduct, source, and/or .a 7. Chemicaland/or physical v8'g Maxinum amount that licensee I special nuclear material '

I

~ form ,.myy possess at any one time I

,) N q'

A. Uranium enriched to b Any, excluding sMdsp'- 4..qder 8,000 thiskilograms license

! maximum 5.0 weight -} powder;3 / ,{ g cerl}ained U-235 I percent in the U-235 2 .o 7 I isotope i, .i )

((

%.\ -m

\(} 4 f n i , .

I I

B. Uranium, any N 35 h B[ Ari.h B ..b."2350 grams l enrichment D' b.i,,

~ N ,- .ij..h:,M.T 34 Gg ' >%

L'

! C. Source materia d [ M . Adyj andlud k metaf' ,C; 50,000 kilograms I (Uranium and Thori:um) J^" powda M { " p

... p I D. Cobalt-60 Seriedse ces N D. 40 millicuries, n

>p' total f } O.

,v I

! 9. Authorized use:

Q For use in acceedance wi I conditions contained in Pr,rt I of theik.thensei( the st(itements, representatbns, s renewal application dated and I February 26, 1982, and supplements dated July 21, 1982; February 21, 1983; .

I May 31, 1984; April 29, June 6, and October 11, 1988; and February 10, and I

March 22, 1989; and letters dated February 29, 1984, January 20, 1986, and l March 30, 1987.

I 10. Authorized place of use: The licensee *c existing facilities in Hematite, Missouri, I as described in the referenced license tenewal application.

11. Quarterly inspections by the Supervisor, NLS&A, or his representative s a b l preplanned and shall be documented. Such documentation shall e ma i 2 years.

I I

I I '

l {'.

I I I (

j i l - -- U

L Nxc rorm 374a U.S. NUCLEAR CE!uLATC3Y CoMMIS$lON l ***' PAGE 2 or 5 ucenso nurnber pacts]l -

MATERIALS LICENSE SNM-33 Amendment No._13 SUPPLEMENTARY SHEET

' ' ' '" li 70-36 lII g

JUL 2 81989 i  !

l l j  !,I, l .

12. A written report shall be made by the NLS&A Supervisor to the Plant Manager every I 6 months reviewing employee radiation exposure (internal and external) and effluent il l 1 release data to determine:

I,

a. if there are any upward trends developing in personnel exposure for identifiable  !

I 4 I

categories of workers, types of operations, or ii; affluent releases; lgl b.

I.

if exposures and releases can be lowered in accordance with the ALARA commitment; c.

and if equipment for efflusot and exposure control'is being properly used, li y

maintained, and inspected.  !

I

' I I i

.I 13.Thelicenseeshallleak.testsealedsourcesinaccordanceOththeenclosed" License l Condition For Leak Testing Sealed Byproduct Material Sourcest3 L

l.

t . .

14. Release of equipment and material from the plant. sits'or to clean areas onsite shall I i

be in accordance with the enclosed " Guidelines for Decontamination of Facilities and lIIl Equipment Prior to Release for Unrestricted Usd ar-Termination of Licenses for Byproduct, Source, or Special Nuclear Material," dated August 1967.

1

!li

15. Pursuant to 10 CFR 20.302; the lidoniaa4Eauthorized ta treat waste Is -

R] and scrap materiais containirg uranium earfched in U-235- and/or source material by I-incineration. -

!1 i - I J

':i.<1!r i

16. Within 60 days of the- dhte of this license. renewal ithe licerrsee shall submit to the j

NRC a description of a-proposed monitoring.progrando deteratine the quantity and ).

l 1 environmental effects af radioactivity on spent lim'estone-rock used as onsite fill i I

I material and to determine the environmental effects of optrdoor storage of the alpha- l' l contaminated material. '/

M ,l i

17. The licensee shall survey spent meshenstrockdis arge from each HF scrubber y

i for beta contamination. Rock with beta contamination which exceeds five times I g

) the background of fresh rock shall not be used for landfill. l l

l3 1

18.Within60daysofthedateofthislicenserenewal,thelicenseeshallsubmittoNMSSfl l

y a plan, including schedule, for the disposal of alpha-contaminated spent limestone rock. j

'g -

1 I

q

19. The licensee shall decontaminate the two evaporation ponds such that the average i I residual contamination in each pond does not exceed the appropriate limit of either 1

250 picocuries of insoluble uranium or 100 picocuries of soluble uranium l of soil. The Tc-99 concentrations in a composite sample for each pond shall be l, .

g determined.

1 ll 3 il il i

\R E

l5 l _ _ _ _ _ _ _ _ _ _ - vN

.___'__________.___________________________________ i

)

] N c rorm anA osa U.S. NUCLEA"I REIULATC'iY CoMMIS5loN pact 3 or 5 pacts l'

i ucense number l l MATERIALS LICENSE SNM-33 Amendment No. 13 lj l SUPPt.EMENTARY SHEET i 1 I 70-36 l l

i M. 2 8 1989 l1

-l  ;

i i I ,

1 20. a. If the radioactivity in plant gaseous effluents exceeds 150 pCi per calendar 1

I I

quarter, the licensee shall, within 30 days, prepare and submit to the l Comission a report which identifies the cause for exceeding the. limit and l i the corrective actions to be taken by the licensee to reduce the release rates. i l

l If the parameters important to a dose assessment change, a raport shall be l

I submitted within 30 days which describes the changes in parameters and includes an estimate of the resultant change in dose comitment y llI I I I

l b.

In the event that the calculated dose to any member of the public in any l i consecutive 12-month period is about~to exceed >the limits specified in 40 CFR g g

190.10, the licensee shall take imediate stepse ta-reduce emissions so as to I

( comply with 40 CFR 190.10. As provided in 40 CFR 190L11, the licensee may I E

petition the Nuclear Regulatory Comission for a variance from the requirements I E

of 40 CFR 190.10. If a petition for a variance is anticipated the licensee shall l submit the request at least 90 days prior to exceeding the limits specified in l i 40 CFR 190.10. ,

.g

.- g i

I

21. The licensee shalT. maintain and axacute the response < measures o'f his Radiological I Contingency Plan submitted to tha:Comission by Tetter dated December 28, 1987. The I l licensee shall aiseLmaintain implementing procedures for his Radiological Contingency l Plan as necessary to implement the. Pian. Therlicensee shall make no change in his l i  ;

Radiological Contingency Plan that wovM decrease the response effectiveness of the I i-I Plan without prior-Commission approval as. evidenced by a license amendment. The I I licensee may make changes to his Radiological / Contingency Plan without prior Commission approval if the changes;do not: decrease the response effectiveness of the l Plan. The licensee shall furnish the Chief', Fuet Cycle Safety Branch, Oivision of ill g

i Industrial and Medical Nuclear Safety, NMSS, U. S.. Nuclear Regulatory Commission, gi n Washington, DC 20555,'a report containing:a_ description.ot"each change within 6 months after the change is,made. I.

l

.[

l 22. At the end of the plant life, tholicensee shall dt> contaminate the facilities y and

) i to the letter dated January 12, 1979, so that these facilities and grounds can be b I released to unrestricted use. The financial commitment to assure that funds will be I 1 available for decommissioning in the letter dated March 8, 1979, is hereby I incorporated as a condition of the license, j

N l 23. The licensee shall continue the soil sampling program for the spent limestone fill i areas, as described in the letter dated February 29, 1984, until discontinuance is  !

p I authorized by the Commission. ;1 I

f lli I I l The report er petition should be submitted to the Director, Office of Nuclear i i Material Safety and Safeguards, with a copy to the Regional Administrator, l' l l Region III. y l 1 ff

,N I l I jI d

)p '

4

) -

___ I

4 i NIC Form 372A U.s. NUCLEWl GEIULATcRY COMMISSloN I is. sal PAat 4 op 5 PAGES uesna number I

! MATERIALS LICENSE SNM-33 Amendment No. 13 l SUPPLEMENTARY SHEET

" " "" l i 70-36 I g

i I JUL 2 81989 4 I

I I I I I I

I I

24. The monitoring program for the spent limestone shall include: 1 I ,

a.

l Continuous air sampling at the center of, and approximately 1 meter above, the  !

i uncovered spent limestone piles for a minimum 2 year period. The weekly samples .i i maybecompositedandanalyzedforurgiumact;vityonaquarterlybasis. The I I

I lower limit of detection shall be 10 pCi/m1, or I I

I

b. Measurement of the uranium activMy on the surface of the spent limestone.

l Prior to conducting such a program, the licensee shall submit the sampling l g and analytical progrem to the NRC for approval.' , i i l

,) I

25. Processing of UF 6 in 10-ton cylinders is not authorized.

j i l

26. The 10-ton UF 6 cylindere shall be equipped with valve prote 2 -

rs.

l'i 1

y 27. The concrete pad for storage of.UFc cylinders and the~ wrrounating area shall be .

l l sloped or graded so that any spil?Nd combustible,flufds would not be confined to I I the storage area.

l

/ff -

I l l 28. No combustibles shall be stored on the concrete padc ---

y i

29. A CO 2 I

i fire extinguisher shell be,readily-awailablesnear the storage pad. I i' t I

3 I I 30. In addition to the controls. in. Sectiom I of t>a enclosure to the letter dated I March 30, 1987, UF cylinders.which are in transport and containing UF heels l shall be either se$1 eat;, in sealed overpacks4 or in sealed vehicles. 6 l g i i , .

' 'I 9 I i 31. Notwithstanding the statement in Section 4.2.3 of the apgrMtation, the I i I k-effective of specifically a unit or by'the authorized an. array of units shall not agerd 0.95 unless Ifcense.

1

' T

'% i ,

.. T l l 32. Nuclear criticality safety evaluatios(perfomed by the licensee in accordance with 3 g.

i Section 2.7, Part I of the application, shall be based on assumptions of optimum i 1 moderation and reflection of individual safe units and of arrays. I I

I I

33. Nuclear criticality safety evaluations involving k-effective calculations performed l by a Nuclear Criticality Specialist shall be independently reviewed and approved by l y

an individual having, as a minimum, the qualifications of a Nuclear Criticality g

Specialist.

I I I

I I

I I I

N I

I I

l i8 a lI l

I i I

jI E

I i' I I I,_ _ _ _ - - _ _ - - - _

n

l NIC Foem 370A U s. NUCLEA3 cEGULATCY COMMIS$10N g iS 84 pggg 3 og g pages ]

Licena number I I

I MATERIALS LICENSE SNM-33 Amendment No. 13 SUPPLEMENTARY SHEET Docket or Referencs number  !

y 70-36 i l I

I a e 8 as l lj i1 l I I l 34. l  !

I For uranium enriched to more than 4.1 w/o U-235, the licensee shall limit the  !

agglomeration / granulation process, each agglomerated powder storage location, and l l the pellat pressing operating to safe mass units as specified in Table 4.2.4, y

Part I of the application. i 1

35. Deleted. I i l <

l l

I I

I

'1 .x' I l ., I I ) I I ., - Q

• I

' / , I l > j',T '

l l .

l y

- i s

, , ~ -. f f/-g '.., I I

l .' f ,'

' I d I

l l

.(l _- -

3 l i .

I

., 7. n , , - I l

~, ,

i *t')i, ,

,. I I

e t .. .

• 3 il ;, i: 1 -

g l

g . . .' :p

',. n

.s s I

f '.' sV y l

')

?

l l

s

.5, 1

.y .1 (

4-llI g

s I .

I I i I I ;I i I 1 I I I E I I I I FOR THE NUCLEAR REGULATORY COMMISSION I I I I I l JUL 2 81989 0 (4

"- l l Jate: l I By: Leland C. Rouse ll i

Division of Industrial and Medical I l Nuclear Safety, NMSS i Washington, DC 20555 )I i

y

.P

,,,____._.A

i O UNITED STATES h

j j NUOLEAR REGULATORY COMMISSION ,

WASHING TON, D. C. 20655 <

\s.....j JUL 2 81989 00CKET NO: 70-36 LICENSEE: CombustionEngineering,Inc.(CE)

Hematite, Missouri  ;

SUBJECT:

SAFETY EVALUATION REPORT, AMENDMENT APPLICATION DATED MARCH 22, 1989, RE: S~.ARTUP AND TEST OF NEW PELLET PRODUCTION LINES AND USE OF ADDITIONAL WAREHOUSE SPACE

Background

On Septenber 30, 1988, CE informed the NRC of the intent to construct additional manufacturing space at the Hematite facility. This new manufacturing space is a large extension that joins together two existing facilities, the pellet plant (Building 255) and the recycle area (Building 240). A major portion of the new manufacturing liner. space will be dedicated to the use of tvc new pellet production .

The remainder of the building is to be used far additional utilities, citices, and material storage. In addition to the construction of this manu-facturing space, the September 30, 1988, letter included a discussion of the expansion of the shipping, receiving, and storage areas. By letter dated Octeber 31, 1988, NRC expressed no objection to CE initiating construction of the t,dditional space provided that soil survey results were submitted for NRC reviea prior to constructing any flooring. CE submitted those results on Decent,er 20, 1988, and on January 24, 1989, Oak Ridge Associated Universities conducted an independent confirmatory survey. Accordingly, on February 24, 1989, CE was informed that there was no objection to the construction of the flooring for the pelletizing and warehouse art,; CE has since completed this construction and is presently installing the v 1 M production lines. In the subject application, CE requests authorization . startup and test the new pellet production lines with depleted uranium'and to use the additional warehouse space for storage of licensed material.

Discussion (

i l

l The new pellet production lines are housed in Building 254 and' consist of  !

blending, pressing, sintering, grinding, and packaging operations. At this i time, the licensee requests authorization to startup and test these lines with depleted uranium. This testing phase will allow CE the opportunity to make any necessary adjustments and resolve any mechanical problems with the new process.

By using depleted uranium, no controls are necessary for nuclear criticality safety. Simi'.ar activities have been conducted in existing facilities, and the radiation safety controls from the license have been extended to Building 254 and are adequate. {

j Bulding 256-2, an extension of the current warehouse Building 256-1, will be '

utilized to store licensed material. The activities that will be authorized have bee.. conducted in existing facilities. Therefore, radiation safety and nuclear criticality safety controls from the license will be extended to Building 256-2 and are adequate.

I

JUL 2 81989 2

CE.

NRC staff prepared an Environmental Ass pur::uant to 10 CFR Part 51.

on May 24, 1989. n mpact was made The Finding was published in the Federal Re

~

~

conclusion / Recommendation aepleted uraptom.This licensing action authorizes the startup and authorization for full production with enriched uraniuCE's by the Commission.

m, has not been approved The staff concludes that the proposed activities will h the public health and safety or the environment application is recommended. , ave no adverse effect on Approval of the amendment The Region III Principal Inspector has no objecti on to this proposed action.

hk David A. McCaughe

.Dd[UraniumFuelSecti on tuel Cycle Safety Branch Division of Industrial and Approved by: Medical Nuclear Safety, NMSS N/ise-George n. sidinger,pection Leader ~

___mm__m_.-_______._____ _ . . _ - _ _ _ _ _ _ _ . _ . _ _ _ . _ _ _ . _ _ _ _ _ _ . . . _ _ - . _ _

.4 - -

1:'

L UNITED STATES CF AMERICA j NUCLEAR REGULATORY COMMISSION -l l

l in the Matter of 1 CCMBUSTION ENGINEERING. INC. Docket No.(s) 70-36-MLA (Hematite Fuel Fabrication Facility  !

License No. SNM-33)  :

)'

CERTIFICATE OF SERVICE I hereby certify that copies of the foregoing NOTE BECHH0EFER TO JULIAN B/15 have been served upon the following persons by U.S. mail, first class, except .

as otherwise noted and in accordance with the requirements of 10 CFR Sec. 2.712.

Administrative Judae Administrative Judge Charles Bechhoefer Jerry R. Kline

. Atomic Safety ano Licensino Board Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commtssion U.S. Nuclear Regulatory Commission Washington, DC 20555 Wasnington, DC 20555 Michael A. Bauser Escuire Office of the General Counsel Newman & Holtzinger, P.C.

U.S. Nuclear Regulatory Commission 1615 L Street, NW Washington,.DC 20555 Washington, DC 20036 Missouri State Senator

- Jeremtah W. (Jay) Nixon 22nd District Martha Dodson Room 429 412 Mississippi State Capitol Crystal City, MD 63019 Jefferson City, MO 65101 Arlene Sandler President Karen Sisk Coalition for the Enytrenment 1123 Wolf Hollow Road St. Louis Chapter Imperial, MO 63052 6267 Delmar Boulevard St. Louis, MD 63130 Dated at Rockville. Md. this 15 day of August 1989

__. .N OfficeofdheSecretary of the Commission

d . . ...